By American Institute of Steel Construction
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Additional info for AISC N690-12 Specification for Safety-Related Steel Structures for Nuclear Facilities
Shop and erection drawings shall have a means of indicating which parts are safety-related. Fabrication 1. Cambering, Curving and Straightening Modify section to read as follows: Local application of heat or mechanical means is permitted to be used to introduce or correct camber, curvature and straightness. The temperature of heated areas shall not exceed 1,100 °F (593 °C) for A514/A514M and A852/A852M steel nor 1,200 °F (649 °C) for other carbon steels. The temperature of heated areas for ferritic, martensitic or duplex stainless steels shall not exceed 600 ºF (316 °C).
Indd 30 7/5/12 1:25 PM 31 CHAPTER NL DESIGN FOR SERVICEABILITY Modify Chapter L of the Specification as follows. Replace preamble with the following: This chapter addresses serviceability design requirements. NL1. General Provisions Replace section with the following: Serviceability of a nuclear plant structure is a state in which the function of a structure, its maintainability, durability and the ability of safety-related systems and components to perform their intended design function are preserved under various loading conditions.
Nonconformance reports shall remain open until a suitable resolution to the cause of the nonconformance has been identified and corrective action documented. User Note: Nonconforming items should be segregated and controlled to prevent inadvertent use or installation. indd 50 7/5/12 1:25 PM 51 APPENDIX N1 DESIGN BY INELASTIC ANALYSIS Modify Appendix 1 of the Specification as follows. Replace preamble with the following: This appendix addresses design by inelastic analysis, in which consideration of the redistribution of member and connection forces and moments as a result of localized yielding is permitted.
AISC N690-12 Specification for Safety-Related Steel Structures for Nuclear Facilities by American Institute of Steel Construction